26-Fe- 56 JAEA EVAL-Jun21 N.Iwamoto DIST-DEC21 20210630 ----JENDL-5 MATERIAL 2631 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-06 Evaluated with CCONE code by N.Iwamoto 21-08 MF3/MT51 was reevaluated by N.Iwamoto 21-09 Secondary energy grids were added below 100keV by N.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 JENDL-5rc1 revised by N.Iwamoto (MF33/MT1-115, MF34/MT2) Evaluated with CCONE-KALMAN MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region (R-M formula) : below 850 keV Resonance paramters were retrieved from JENDL-4.0/1/. The direct and semi-direct capture cross sections were added in the energy region of 1e-5eV to 20MeV/2/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.47876E+01 Elastic 1.21924E+01 n,gamma 2.59507E+00 1.33901E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /3/. Cross sections in the range of 0.85 to 7.125 MeV were taken from JENDL-4.0. MT= 2 Elastic scattering cross section Calculated with CCONE code /3/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT51 below 3 MeV was replaced into Dupont et al./4/ with normalization. MT52 below 4 MeV was replaced into Negret et al./5/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /3/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /3/. MT=111 (n,2p) cross section Calculated with CCONE code /3/. MT=112 (n,pa) cross section Calculated with CCONE code /3/. MT=115 (n,pd) cross section Calculated with CCONE code /3/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /3/. The Legendre coefficients were derived by the data of Perey et al./6/, Kinney et al./7/, and Smith et al./8/ in the energy ranges of 0.3 to 0.85, 0.85 to 2.5, and 2.5 to 4MeV. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=111 (n,2p) reaction Calculated with CCONE code /3/. MT=112 (n,pa) reaction Calculated with CCONE code /3/. MT=115 (n,pd) reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. MF= 8 Information on decay data MT=4 (n,n') reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MT=111 (n,2p) reaction Decay chain is given in the decay data file. MT=112 (n,pa) reaction Decay chain is given in the decay data file. MT=115 (n,pd) reaction Decay chain is given in the decay data file. MF=33 Covariances of neutron cross sections Covariances were given to all the cross sections by using KALMAN code and the covariances of model parameters used in the cross-section calculations. MF=34 Covariances for Angular Distributions MT= 2 Elastic scattering Covariances were given only to P1 components. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : A.J.Koning and J.P.Delaroche/9/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/9/ deuteron: Y.Han et al./10/ triton : folding OMP, A.J.Koning and J.P.Delaroche/9/ He-3 : Y.Xu et al./11/ alpha : L.McFadden and G.R.Satchler/12/ modified * Level scheme of Fe-56 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.846780 2 + 2 2.085100 4 + 3 2.657590 2 + 4 2.941500 0 + 5 2.959970 2 + 6 3.120110 1 + 7 3.122970 4 + 8 3.369950 2 + 9 3.388550 6 + 10 3.445350 3 + 11 3.448410 1 + 12 3.600210 2 + 13 3.605690 2 + 14 3.610210 0 + 15 3.744130 2 + 16 3.755570 6 + 17 3.759600 1 - 18 3.829770 2 + 19 3.856490 3 + 20 4.048890 3 + 21 4.085930 2 + 22 4.100360 4 + 23 4.119940 3 + 24 4.298100 4 + 25 4.302000 0 + 26 4.320000 2 + 27 4.368130 3 - 28 4.394930 3 + 29 4.401270 2 + 30 4.447700 1 - 31 4.458530 4 + 32 4.509560 3 - 33 4.539500 2 + 34 4.554770 4 + 35 4.608560 2 + 36 4.610820 4 + 37 4.620000 3 - 38 4.658260 2 + 39 4.673410 2 - 40 4.683040 3 + ----------------------- * Level density parameters (Gilbert-Cameron model/13/) Energy dependent parameters of Mengoni-Nakajima/14/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Fe-57 8.315 1.589 -1.312 1.366 -2.315 12.701 3.059 Fe-56 8.265 3.207 -2.152 1.503 -1.634 17.526 4.683 Fe-55 8.333 1.618 -2.981 1.428 -1.607 14.443 3.860 Mn-56 8.088 0.000 -0.645 1.291 -3.292 9.240 1.780 Mn-55 8.148 1.618 -1.124 1.431 -3.019 13.792 3.046 Mn-54 7.628 0.000 -2.202 1.423 -2.764 10.850 2.715 Cr-55 9.777 1.618 0.422 0.817 0.473 6.002 3.183 Cr-54 9.675 3.266 -0.310 1.049 0.511 10.460 4.256 Cr-53 7.868 1.648 -1.137 1.298 -1.087 10.541 3.435 Cr-52 7.792 3.328 -1.323 1.378 0.001 13.627 4.100 --------------------------------------------------------- * Gamma-ray strength functions for Fe-57 E1: hybrid model(GH)/15/ ER= 16.79 (MeV) EG= 5.69 (MeV) SIG= 31.23 (mb) ER= 19.67 (MeV) EG= 7.69 (MeV) SIG= 62.46 (mb) M1: standard lorentzian model(SLO) ER= 10.65 (MeV) EG= 4.00 (MeV) SIG= 1.82 (mb) E2: standard lorentzian model(SLO) ER= 16.37 (MeV) EG= 5.43 (MeV) SIG= 1.30 (mb) References 1) K.Shibata et al., J. 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